Presentation Information
[1K06]Study on estimation of radioactivity concentration of biological shielding at Fukushima Daiichi Nuclear Power Station(3) Neutron flux distribution applying variance reduction method
*Masaya SEKI2, Yoshikazu KOMA1, Takeshi OKADA1, Youko TAKAHATAKE1, Tsutomu ISHIGAMI2, Takeshi SUGITA2, Tsutomu OKAMOTO2, Hiroki NEMOTO2 (1. JAEA, 2. NAIS, Co., Inc.)
Keywords:
Fukushima Daiichi Nuclear Power Station,Radioactive waste,Activation calculation,Monte Carlo method,Variance reduction method
Constructed 3D models of the Fukushima Daiichi Nuclear Power Station Unit 2 ,and the neutron flux distribution required for the activation calculation was calculated using a Monte Carlo calculation code.
The calculation target region was set to the biological shield concrete around the reactor , and the optimization target was divided into three regions to optimize the variance reduction method.
The calculation target region was set to the biological shield concrete around the reactor , and the optimization target was divided into three regions to optimize the variance reduction method.
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